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Oral presentation

Study on non-destructive measurement by using fast neutron direct interrogation method for fuel debris

Maeda, Makoto; Furutaka, Kazuyoshi; Kureta, Masatoshi; Ozu, Akira; Tobita, Hiroshi; Komeda, Masao; Hattori, Kentaro

no journal, , 

no abstracts in English

Oral presentation

Design of a JT-60SA Thomson scattering system

Tojo, Hiroshi; Hatae, Takaki; Sakuma, Takeshi; Hamano, Takashi; Itami, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Corrosion properties of RAFM, F82H in high temperature pressurized water

Nakajima, Motoki

no journal, , 

Reduced activation ferritic/martensitic steel, F82H is the most promising candidate structural material for fusion blanket. Water-cooled ceramic breeder blanket is an attractive concept for its compactness and its compatibility with the technologies in conventional pressurized water reactor (PWR). For blanket application, the structural material is required to be as thin as possible for tritium breeding. On the other hand, it is also required the pressure tightness which could withstand internal pressure of 15 MPa. Therefore it is necessary to determine corrosion allowance for cooling tubes precisely. This work reports corrosion properties of F82H in high temperature pressurized water. Moreover, the effects of water flow on corrosion properties were investigated using rotating disk specimen in autoclave.

Oral presentation

Remote control methods for a robot arm working in a radiation environment

Maruyama, Takahito; Noguchi, Yuto; Ueno, Kenichi; Takeda, Nobukazu; Kakudate, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Development of radiation hard components for ITER blanket remote handling system

Saito, Makiko; Anzai, Katsunori; Maruyama, Takahito; Noguchi, Yuto; Takeda, Nobukazu; Kakudate, Satoshi

no journal, , 

no abstracts in English

Oral presentation

Study on structural analysis and in-situ diagnostic technique for the lead-bismuth spallation target in JAEA

Wan, T.; Kogawa, Hiroyuki; Obayashi, Hironari; Iwamoto, Hiroki; Takei, Hayanori; Sasa, Toshinobu; Maekawa, Fujio

no journal, , 

Oral presentation

Development of nuclear data processing system FRENDY

Tada, Kenichi

no journal, , 

In JAEA, the nuclear data processing system FRENDY (FRom Evaluated Nuclear Data librarY to any application) has been developed. In this presentation, the overview and verification of FRENDY is described.

Oral presentation

Solubility of selenium in the presence of iron under reducing conditions

Doi, Reisuke; Uchikoshi, Keiji*; Beppu, Hikari*

no journal, , 

In order to determine the solubility-controlling solid of Se under reducing conditions, solubility experiments of Se were performed from oversaturation direction in the presence of Fe under reducing conditions. The Se concentration as a function of equilibration periods suggested the attainment of equilibrium in our system within a month. Only FeSe$$_{2}$$ was detected as the Se solid phase by XRD analysis of the solid samples from the equilibrated suspensions. Interpretations using the specific ion interaction theory model showed that the relationship between Eh and the measured concentrations of Se and Fe could be interpreted well by the dissolution reaction of FeSe$$_{2}$$. Therefore, we conclude that FeSe$$_{2}$$ is most likely the solubility-controlling solid of Se under these conditions.

Oral presentation

Study of decontamination methods with microbubbles

Yamamoto, Keisuke; Aoyama, Yoshio

no journal, , 

no abstracts in English

Oral presentation

Mechanismic study on Rh(III) adsorption using carbobetaine type ion-exchange resin

Suzuki, Tomoya; Morita, Keisuke; Sasaki, Yuji; Matsumura, Tatsuro

no journal, , 

no abstracts in English

Oral presentation

pH and ionic strength dependency of Nb solubility

Iwata, Hajime; Kitamura, Akira

no journal, , 

The solubility of Nb was measured using oversaturation and undersaturation method. Compared with the values evaluated using JAEA-TDB, in the OS method a similar solubility was observed, and the measured values in the US method were around three orders magnitude below the evaluated values. It suggests that the solubility limiting solid differ between OS and US method.

Oral presentation

Fabrication of insert coil with ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

no journal, , 

no abstracts in English

Oral presentation

Preliminary study for halogen free dissolution techniques for determination of radioactive waste sampling

Shimizu, Koki; Koyama, Hayato; Aoyama, Yoshio

no journal, , 

no abstracts in English

Oral presentation

Evaluation of retention properties for metal ions in geopolymer matrix

Sato, Junya; Suzuki, Shinji; Sakakibara, Tetsuro; Meguro, Yoshihiro; Nakazawa, Osamu

no journal, , 

no abstracts in English

Oral presentation

Benchmark calculation for burnup of BWR fuel assembly with MOSRA-SRAC

Kojima, Kensuke; Okumura, Keisuke

no journal, , 

The MOSRA system has been developing to improve the applicability of the neutronic characteristic analyses. The cell calculation module MOSRA-SRAC is a core module of MOSRA, and applicability tests for realistic problems are required. As a test, we joined the benchmark "Burnup Credit Criticality Benchmark Phase IIIC." The benchmark requested the neutronic characteristics for a BWR fuel assembly with gadolinium, which had been used in the TEPCO's Fukushima Daiichi Nuclear Power Station. Because of a restriction of MOSRA-SRAC, the geometry was partially homogenized. To verify the module's applicability including the homogenization effects, the multiplication factor and the nuclide compositions were compared with the well-validated code MVP-BURN. As the results, the applicability of MSORA-SRAC for the assembly was verified. Additionally, it was also shown that the homogenization effects were smaller than the difference due to the calculation methods.

Oral presentation

Development of uniform beam production in ITER class negative ion source

Yoshida, Masafumi; Hanada, Masaya; Kojima, Atsushi; Kashiwagi, Mieko; Tobari, Hiroyuki; Hiratsuka, Junichi; Akino, Noboru; Endo, Yasuei; Komata, Masao; Mogaki, Kazuhiko; et al.

no journal, , 

no abstracts in English

Oral presentation

Study on a fabrication method of nitride fuels for MA transmutation via precursor carbon containing nitrate gel-spheres produced by a wet process using a dehydration reaction

Mizutani, Yoshitaka*; Honda, Masaki*; Nishi, Tsuyoshi*; Hayashi, Hirokazu

no journal, , 

no abstracts in English

Oral presentation

Reaction products at interface region between concrete and core melt

Sudo, Ayako

no journal, , 

no abstracts in English

Oral presentation

Development of three way valve using bellows seal for pulsation in vessels of high active waste solution

Morimoto, Kenji; Isozaki, Naohiko; Yasuo, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Cryogenic system and piping for JT-60SA

Natsume, Kyohei; Yoshida, Kiyoshi; Kizu, Kaname; Koide, Yoshihiko

no journal, , 

no abstracts in English

27 (Records 1-20 displayed on this page)